ML20197E685
| ML20197E685 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/01/1986 |
| From: | Bruce Bartlett, Cummins J, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20197E630 | List: |
| References | |
| 50-482-86-05, 50-482-86-5, NUDOCS 8605150298 | |
| Download: ML20197E685 (8) | |
See also: IR 05000482/1986005
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APPEtiDIX B
U.S. NUCLEAR REGULATORY C0tHISSION
REGION IV
NRC Inspection Report: 50-482/86-05
LP:
Docket: 50-482
Licensee:
Kansas Gas and Electric Company (KG&E)
Post Office Box 208
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Wichita, Kansas 67201
Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas
Inspection Conducted: March 1-31, 1986
Inspectors:
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J. I. IUmmins, Sen'ior Rbsident Inspector, Operations
Date
tilb
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B. L. Bartlett, Residel[t' Reactor Inspector,
Date
Operations
Approved:
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D. R. Hunter, Chief, Project Section B, Reactor
Uate
Projects Branch
Inspection Summary
Inspection Conducted March 1-31, 1986 (Report 50-482/86-05)
Areas Inspected:
Routine, unannounced inspection including followup on
previously identified NRC items, operational safety verification, engineered
safety features system walkdown, onsite followup of events, monthly
surveillance observation, monthly maintenance observation, and plant tours.
Results: Within the seven areas inspected, one violation was identified
(failure to document the performance of a surveillance test in accordance with
procedure, paragraph 6). One open item is identified in paragraph 5.
8605150298 860507
ADOCK 05000482
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DETAILS
1.
Persons Contacted
Principal Licensee Personnel
- J. A. Bailey, Interim Site Director
- F. T. Rhodes, Plant Manager
M. Estes, Superintendent of Operations
M. D. Rich, Superintendent of Maintenance
- M. G. Williams, Superintendent of Regulatory, Quality, and
Administrative Services
0. L. Maynard, Manager, Licensing
J. Goode, Licensing
- K. Peterson, Licensing
- G. Pendergrass, Licensing
- W. M. Lindsay, Supervisor, Quality Systems
C. E. Parry, Superintendent-Quality Systems Engineering
- C. J. Hoch, QA Technologist
R. D. Flannigan, Supervisor, Compliance Engineering
- A. A. Freitag, Manager, Nuclear Plant Engineering-WCGS
- C. M. Herbst, Project Engineer, Bechtel
M. Megehee, Compliance Engineer
- W. J. Rudolph, QA Manager
The NRC inspectors also contacted other members of the licensee's staff
during the inspection period to discuss identified issues.
- Denotes those personnel in attendance at the exit meeting held on
April 2, 1986.
2.
Followup on Previously Identified NRC Items
(Closed) Violation (50-482/EA85-127-A and 50-482/8535-01): Violation
Of Technical Specification-Centrifugal Charging Pump (CCP) Inoperable.
The violation involved a failure to restore CCP '1A' to operable status
within the time limit of the action statement for Technical Specifica-
tion 3.5.2.
The NRC inspector reviewed the licensee's response and veri-
fied that changes have been made to STS BG-100A and STS BG-1008 to correct
ambiguous statements; that Licensee Event Report (LER) 85-063-00 was placed
in the operations required reading and was signed off as being read by the
appropriate shift personnel; that shift supervisors were trained in post-
test review requirements; and by walkdowns of selected engineered safety
features (ESF) systems that Technical Specification requirements were
being met. This violation is closed.
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(Closed) Violation (50-482/EA85-127-B and 50-482/8535-02):
Failure to
Observe Protective Clothing Requirements Of a Radiation Work Permit.
The violation involved a radiation worker entering a radiologically
controlled work area without donning the required protective clothing.
The NRC inspector verified that this event was documented in accordance
with Procedure ADM 03-006, " Notice of Radiological Work Practice
Violation," and that the station operator was counseled on the
importance of complying with RWP procedures.
This violation is closed.
(Closed) Violation (50-482/EA85-127-C and 50-482/8535-03):
Violation
Of Technical Specification-Containment Fire Detection Instrumentation
Out-0f-Service.
The violation involved failure to establish a fire watch or monitor
containment air temperature in accordance with Technical Specifica-
tion 3.3.3.8 when the fire detection instrument for Fire Detection
Zone 201 was inoperable. The NRC inspector verified that Procedure
ADM 02-010, " Shift Relief and Turnover," and LER 85-070-00 were assigned
and read as required reading.
In addition, the NRC inspector, through
interviews with licensed operators, ve.ified that oncoming crew members
were cognizant of plant equipment status prior to assuming shift duties.
This violation is closed.
(Closed) Violation (50-482/EA85-127-0 and 50-482/8535-04):
Failure To
Follow Installation Criteria For Various Conduits.
The violation involved using an unapproved method to install a flexible
conduit. The NRC inspector reviewed the management letter that was sent to
all station employees.
Field _ inspections by the NRC inspector of
selected items revealed no other violations of this type.
This item is
closed.
(Closed) Violation (50-482/8537-01):
Nonseismic Glass Level Gauge Not
Isolated.
The violation involved a failure to isolate a seismic portion of a
safety-related system from a nonseismic portion.
The NRC inspector
verified that Checklist (CKL) EG-120 had been revised to show the four
valves locked closed; that the five additional tanks that were-
identified each had their appropriate checklist revised; that Procedure
ADM 02-102, " Cont.01 of Locked Component Status," had been revised to
show proper positioning; and through field inspection verified that the
appropriate valves were closed and locked.
This item is closed.
No violations or deviations were identified.
3.
Operational Safety Verification
The NRC inspectors verified that the facility was being operated safely
and in conformance with regulatory requirements by direct observation
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of licensee facilities, tours of the facility, interviews and discussions
with licensee personnel, independent verification of safety system status
and limiting conditions for operations, and by reviewing facility records.
The NRC inspectors, by observation, interview of personnel, and review of
documents, verified the physical security plan was being implemented in
accordance with the security plan and that radiation protection activities
were controlled.
By observing valve position, electrical breaker position, and control
room indication, the NRC inspectors confirmed the operability of the
accumulator safety injection system and the coolant charging system.
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The NRC inspectors also visually inspected safety components for leakage,
physical damage, and any other impairment that could prevent them from
performing their designed function.
No violations or deviations were identified.
4.
Engineered Safety Features (ESF) System Walkdown
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The NRC inspectors verified the operability of ESF systems by walking
down selected accessible portions of the systems.
The NRC inspectors
verified valves and electrical circuit breakers were in the required
position, power was available, and valves were locked where required.
The NRC inspectors also inspected system components for damage or other
conditions that could degrade system performance.
The ESF systems listed below were walked down during this inspection
report period:
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Refueling Water Storage (BN)
High Pressure Coolant Injection (EM)
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Emergency Fuel Oil (JE)
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No violations or deviations were identified.
5.
Onsite Followup of Events
The NRC inspectors performed onsite followup of nonemergency events that
occurred during this report period. The NRC inspectors (when available)
observed control room personnel response, observed instrumentation
indicators of reactor plant parameters, reviewed logs and computer
printouts, and discussed the event with cognizant personnel.
The NRC
inspectors verified the licensee had responded to the event in accordance
with procedures and had notified the NRC and other agencies as required in
a timely fashion.
Engineered Safety Feature actuations that occurred during the report
period are listed in the table below. Where applicable, the NRC
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inspector will review the LER for each of these events and will report
any findings in subsequent NRC inspection reports.
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1
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Date
Event *
Plant Status
Cause
3/26/86
CRVIS
Mode 1
Blown Fuse on
Chlorine Detector
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3/27/86
CRVIS, CPIS,
& FBVIS
Mode 1
Failed Power Supply
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3/27/86
AFW, Actuation
With LSP Switch-
1
over to ESW
Mode 1
Personnel Error
- Event
CRVIS - control room ventilation isolation signal.
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CPIS - containment purge isolation signal
FBVIS - fuel building ventilation isolation signal
LSP - low suction pressure
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ESW - essential service water
Selected NRC inspector observations:
On March 27, 1986, at 1813 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.898465e-4 months <br /> a CRVIS, CPIS, and FBVIS were generated
when the -15 volt DC power supply failed in Cabinet SA 036D. After
approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of reviewing prints, the instrumentation and control
(I&C) personnel trouble shooting the problem removed a fuse in a 120V AC
circuit and when it was replaced, an AFW actuation occurred along with an
AFW low suction pressure automatic switchover to ESW. As designed, only
the '1A' train ESW pump started. The balance of plant (80P) operator
shut down the three running AFW pumps before any ESW water was placed in
the steam generators (S/Gs).
Operations personnel flushed the ESW water out of '1A' motor driven AFW
pump and the turbine driven AFW pumps (TDAFWP) using 1-inch drain lines and
gravity feed from the condensate storage tank (CST). After chemistry
samples taken from the AFW system and analyzed indicated the system was
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again clean, the AFW pumps were run in their normal modes supplying water
to the S/Gs to ensure all ESW water was flushed from the AFW system.
Currently an evaluation is in progress to determine the corrective action
required to ensure that the' long term operation of the AFW system has not
been degraded through chemical reactions to the ESW water. The NRC
inspector will follow up this evaluation to verify proper corrective
action has been taken. Using Work Request (WR) 01336-86, I&C replaced the
failed power supply on March 28, 1986. This will be tracked as Open Item
No. 50-482/8605-02.
No violations or deviations were identified.
6.
Monthly Surveillance Observation
The NRC inspectors observed selected portions of the performance of.
surveillance testing and/or reviewed completed surveillance test procedures
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to verify that surveillance activities were performed in accordance with
TS requirements and administrative procedures. The NRC inspectors
considered the following items while inspecting survePlance activities:
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Testing was being accomplished by qualified personnel in accordance
with an approved procedure.
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The surveillance procedure conformed to TS requirements.
Required test instrumentation was calibrated.
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Technical Specification limiting conditions for operation (LCO) were
satisfied.
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Test data was accurate and complete. Where appropriate, the NRC
inspectors performed independent calculations of selected test data
to verify their accuracy.
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The performance of the surveillance procedure conformed to applicable
administrative procedures.
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The surveillance was performed within the required frequency and the
test results met the required limits.
Surveillances witnessed and/or reviewed by the NRC inspectors are listed below:
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STS IC-920, Revision 4, " Containment Hydrogen Analyzer GS 065A
Calibration Test"
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STS EJ-100A, Revision 0, "RHR System Inservice Pump '1A' Test"
STS GK-001B, Revision 5, " Control Room Emergency Ventilation System"
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STS IC-913, Revision 4, " Containment Hydrogen Analyzer GS 065B
Calibration Test"
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STS88-004, Revision 4, "RCS Water Inventory Balance"
Selected NRC inspector observations:
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On March 26, 1986, the NRC inspector observed a portion of the
performance of STS GK-001B and then reviewed the surveillance proce-
dure.
During this review, the NRC inspector observed that even though
the surveillance had been in progress for a number of hours, Section 3,
" Initial Conditions," had not been signed off as completed. When the
supervising operator was informed, he stated, that when the previous
shift had started the surveillance, they had missed signoff of this
section. This failure to document the performance of a Section 3 of
the surveillance in accordance with procedure is an apparent violation
(50-482/8605-01).
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7.
Monthly Maintenance Observation
The NRC inspector observed maintenance activities performed on
safety related systems and components to verify that these activities
were conducted in accordance with approved procedures, Technical
Specifications, and applicable _ industry codes and standards.
The following
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elements were considered by the NRC inspector during the observation and/or
review of the maintenance activities:
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LCO were met and, where applicable, redundant components were
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Activities complied with adequate administrative controls.
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Where required, adequate, approved, and up-to-date procedures were
used.
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Craftsmen were qualified to accomplish the designated task and
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technical expertise (i.e., engineering, health physics, operations)
were made available when appropriate.
Replacement parts and materials being used were properly certified.
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Required radiological controls were implemented.
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Fire prevention controls were implemented where appropriate.
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Required alignments and surveillances to verify post maintenance
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operability were performed.
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Quality control hold points and/or checklists were used when
appropriate and quality control personnel observed designated work
activities.
Selected portions of the maintenance activities accomplished on the work
requests (WR) listed below were observed and related documentation reviewed
by the NRC inspector:
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WR 01305-86, "BB FB-426A, Replace NAll Card"
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WR 01112-86, " Containment Hydrogen Analyzer GS 065A, Zero Reading Is
Off Scale"
WR 01336-86, "SA 036D, -15 Volt DC Power Available Light Not-
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Illuminated, All Red Train Process Monitor Bistables Tripped"
No violations or deviations were identified.
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8.
Plant Tours
At various times during the course of the inspection period, the NRC
inspectors conducted general tours of the reactor building, auxiliary
building, radwaste building, fuel handling building, control building,
turbine building, and the secured area surrounding the buildings.
During
the tours, the NRC inspectors observed housekeeping practices, fire
protection barriers and equipment, and maintenance on equipment.
The NRC
inspectors also discussed various subjects with licensee personnel.
No vialations or deviations were identified.
9.
Open Items
Open items are matters which have been discussed with the licensee, which
will be reviewed further by the inspector, and which involve some action
on the part of the NRC or licensee or both.
An open item disclosed during
the inspection is discussed in paragraph 5.
10.
Exit Meeting
The NRC inspectors met with licensee personnel to discuss the scope and
findings of this inspection on April 2, 1986.
The NRC inspectors also
attended entrance / exit meeting with another NRC region-based inspector
identified below:
Inspection
Area
Inspection
Period
Inspector
Inspected
Report No.
3/10-14/86
C. Hackney
Emergency
86-06
Preparedness
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